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SAFETY STUDIES ON HYDROGEN PRODUCTION SYSTEM WITH A HIGH TEMPERATURE GAS-COOLED REACTOR  

TAKEDA TETSUAKI (HTGR Performance and Safety Demonstration Group Nuclear Applied Heat Technology Division Nuclear Science and Engineering Directorate Japan Atomic Energy Agency)
Publication Information
Nuclear Engineering and Technology / v.37, no.6, 2005 , pp. 537-556 More about this Journal
Abstract
A primary-pipe rupture accident is one of the design-basis accidents of a High-Temperature Gas-cooled Reactor (HTGR). When the primary-pipe rupture accident occurs, air is expected to enter the reactor core from the breach and oxidize in-core graphite structures. This paper describes an experiment and analysis of the air ingress phenomena and the method fur the prevention of air ingress into the reactor during the primary-pipe rupture accident. The numerical results are in good agreement with the experimental ones regarding the density of the gas mixture, the concentration of each gas species produced by the graphite oxidation reaction and the onset time of the natural circulation of air. A hydrogen production system connected to the High-Temperature Engineering Test Reactor (HTTR) Is being designed to be able to produce hydrogen by themo-chemical iodine-Sulfur process, using a nuclear heat of 10 MW supplied by the HTTR. The HTTR hydrogen production system is first connected to a nuclear reactor in the world; hence a permeation test of hydrogen isotopes through heat exchanger is carried out to obtain detailed data for safety review and development of analytical codes. This paper also describes an overview of the hydrogen permeation test and permeability of hydrogen and deuterium of Hastelloy XR.
Keywords
High-Temperature Gas-Cooled Reactor; Passive Safe Technology; Natural Circulation; Molecular Diffusion; Hydrogen Production System; Hydrogen Permeation; Hastelloy XR; Permeability;
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1 T. Takeda, J. Iwatsuki, and T. Nishihara, 'Study on hydrogen permeation through high-temperature tube in the HTTR heat utilization system,' Proc. 6th International Conference on Nuclear Engineering, San Diego, CA, USA, ICONE-6125 (1998)
2 R. E. Walker, N. deHaas, and A. A. Westenberg, 'Measurements of multicomponent diffusion coefficients for the CO2-He-N2 system using the point source technique,' J. Chem. Phys., 32, 1314-1316 (1960)   DOI
3 S. V. Patankar, Numerical Heat Transfer and Fluid Flow, McGraw-Hill, New York (1980)
4 D. B. Spalding, 'A novel finite-difference formulation for differential expressions involving both first and second derivatives,' Int. J. Num. Methods Eng., 4, 551 (1972)   DOI   ScienceOn
5 K. Sawa, H. Mikami, and S. Saito, 'Analytical method and results of off-site exposure during normal operation of high temperature engineering test reactor (HTTR),' Energy, 16, 459-470 (1999)   DOI   ScienceOn
6 H. Ohashi, et al., 'Performance test results of mock-up test facility of HTTR hydrogen production system,' Proc. 11th International Conference on Nuclear Engineering, Tokyo, Japan, ICONE11-36059, 2003
7 R. K. Shah and A. L. London, Advances in Heat Transfer : Laminar Flow Forced Convection in Ducts, p. 78, Academic, New York (1978)
8 W. A. Swansiger and R. Bastasz, 'Tritium and deuterium permeation in stainless steels: Influence of thin oxide films,' J. of Nucl. Mater. 85&86, 335-339 (1979)   DOI   ScienceOn
9 H. Katsuta and K. Furukawa, 'Hydrogen and deuterium transport through type 304 stainless steel at elevated temperatures,' J. of Nucl. Sci. and Technol., 18, 143-151 (1981)   DOI
10 K. Kunitomi, et al., 'Thermal transient analyses during a depressurization accident in the HTTR,' JAERI-M, 91-163 (1991), in Japanese
11 R. C. Reid, J. M. Prausnitz, and T. K. Sherwood, The Properties of Gases and Liquids 3rd Edn., 37-40, 226, 410-414, 470-474, 548-565, McGraw-Hill, New York (1977)
12 C. R. Wilke, 'Diffusional properties of multicomponent gases,' Chem. Eng. Prog., 46, 95-104 (1950)
13 D. F. Fairbanks and C. R. Wilke, 'Diffusion coefficients in multicomonent gas mixture,' Ind. Eng. Chem., 42, 471-475 (1950)   DOI
14 T. Takeda and M. Hishida, 'Study on the passive safe technology for the prevention of air ingress during the primary-pipe rupture accident of HTGR,' Nucl. Eng. Des., 200, 251-259 (2000)   DOI   ScienceOn
15 Y. Mori and T. Nakada, BNES Conf. on the HTR and Process Appl., Inst. of Civil Eng., Westminster, London, Paper 49, 1974
16 T. Takeda and J. Iwatsuki, 'Counter-permeation of deuterium and hydrogen through INCONEL600,' Nucl. Technol., 146, 83-95 (2004)   DOI
17 R. A. Strehlow and H. C. Savage, 'The permeation of hydrogen isotopes through structural metals at low pressures and through metals with oxide film barriers,' Nucl. Technol., 22, 127-137 (1974)   DOI
18 H. D. Rohrig, et al., 'Studies on the permeation of hydrogen and tritium in nuclear process heat installations,' Nucl. Eng. Des., 34, 157-167 (1975)   DOI   ScienceOn
19 K. Masui, H. Yoshida, and R. Watanabe, 'Hydrogen permeation through Iron, Nickel, and heat resisting alloys at elevated temperatures,' Trans. ISIJ, 19, 547-552 (1979)
20 T. Namba, et al., 'Hydrogen permeation through Nickel and Hastelloy X,' J. Japan Inst. Metals, 42, 374-380 [in Japanese] (1978)   DOI
21 W. M. Robertson, Proc. International Meeting on Hydrogen in Metals, Julich, Germany, II, 449 (1972)
22 T. Takeda, J. Iwatsuki, and Y. Inagaki, 'Permeability of hydrogen and deuterium of Hastelloy XR,' J. Nucl. Mater., 326, 47-58 (2004)   DOI   ScienceOn
23 K. Hada, Y. Motoki, and O. Baba, Japan Atomic Energy Research Institute, JAERI-M 90-148 [in Japanese] (1990)
24 T. Takeda, et al., 'Analysis of air ingress process during the primary-pipe rupture accident of the HTGR,' Proc. 3rd AERI Symp. on HTGR Technologies, JAERI-Conf 96-010, 275-288, 1996
25 K. Kunitomi, et al., 'Depressurization accident analysis for the HTTR by the TAC-NC,' Energy, 16, 471-480 (1991)   DOI   ScienceOn
26 T. Takeda and M. Hishida, 'Studies on molecular diffusion and natural convection in a multicomponent gas system,' Int. J. of Heat and Mass Transfer, 39, 527-536 (1996)   DOI   ScienceOn
27 M. Hishida, T. Takeda, and S. Takenaka, 'Air ingress during the primary-pipe rupture accident of an HTGR,' Proc. 3rd JSME/ASME Joint International Conference on Nuclear Engineering, Tokyo, Japan, 2, 1093-1100, 1995
28 T. Takeda, et al., 'Study on tritium/hydrogen permeation in the HTTR hydrogen production system,' Proc. 7th International Conference on Nuclear Engineering, Tokyo, Japan, ICONE-7102, 1999
29 T. Takeda and M. Hishida, 'Studies on diffusion and natural convection of two-component gases,' Nucl. Eng. Des., 135, 341-354 (1992)   DOI   ScienceOn
30 H. Ohashi, et al., Proc. 13th International Conference on Nuclear Engineering, Beijing, China, May 16-20, ICONE13-50536, 2005
31 S. Saito, et al., 'Design of High Temperature Engineering Test Reactor (HTTR),' JAERI-1332, Japan Atomic Energy Research Institute (1994)
32 S. Shiozawa, et al., 'Research and development of HTTR hydrogen production system in JAERI,' Proc. 12th Pacific Basin Nuclear Conference, Seoul, Korea, 2, 1007-1018 (2000)
33 Y. Inagaki, et al., 'Out-of-pile demonstration test of hydrogen production system coupling with HTTR,' Proc. 7th International Conference on Nuclear Engineering, Tokyo, Japan, ICONE-7101, 1999